ML18095A519

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Proposed Tech Spec Table 4.3-1 Re Reactor Trip Sys Surveillances
ML18095A519
Person / Time
Site: Salem  
Issue date: 10/02/1990
From:
Public Service Enterprise Group
To:
Shared Package
ML18095A518 List:
References
NUDOCS 9010150173
Download: ML18095A519 (7)
v • d • e


Text

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  • *-* ~6cL ATTACHMENT 2 1

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FUNCTIONAL IJNIT

18.

Turbine Trip Low Autostop Oil Pressure Turbine Stop Valve Closure EGJ:

  • 19.

Sc.tfety Injection Input from-~

w.

Reactor Coolant l'ump Dreake1 Position Trip (above l'-7)

21.

Reactor Trip Breakers

22.

Automatic Trip Logic REACTOR TJ{ll' __ SYSTEM I NSTkUMENTAT ION TOTAL NUMllER Ol~_~llAN~~LS _,_

  • ~

')

CHANNELS TO THIP 2

4 MINIMUM CHANNELS OPt:.HABLE j

1/1.Jre...lter lJl!l' UlJefd-ti ug 1001:'

APl'LI CAULE

- _MQW*:!:!_ ___ _

I*~

711 Lil 11

c:

z

-i w

I I-'

N

~

m

I Q.

ffi

I rt
z 0

'fABL£ 4.3-1 (Continued]

REACTOR 'I'Rl P_ -~X~fl' EM l NSTRUMENT AT JON SURV El LLANCE REQUIREMENTS FUNCTIONAL UNIT

13.

Loss of Flow - Two Loops

14.

Steam Generator Water Level--

Low-Low

15.

Steam/Feedwater Flow Mismatch &

Low Steam Ge11er;at:ur Water Level

16.

Undervoltage - Reactor Coolant Pumvs

17.

Underfrequency - Reactor Coolant Pumps

18.

Turbine Trip A.

Low Autostop Oil Pressure B.

Turbine Stop Valve Closure ESP

19.

Safety Injection Input from ~

20.

Reactor Coolant Pump Breaker Position Trip

21.

Reactor Trip Breaker

22.

Automatic Trip Logic CllANNEL CllECK s

s N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CALIBRATION R

R R

R' N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL TEST N.A.

M M

M S/U( 1)

S/U(1}

M(4)..t"'[ZS]

R S/U( 10),

M(11,13},

SA(12,13) and R(14)

M(5)

MOUES IN WHICH SURVEILLANCE REQUIRED

. I 1, L I '

I, 2

1. 2 1
  • 2 N.A.

1, 2 and*

1, 2 and*

(1)

.._;'UjL.C.

~ *.J-1 \\t...onc1nueaJ NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

(2)

Heat balance only, above 15% of RATED THERMAL POWER.

(3)

(4)

(5)

(6)

(7)

Compare incore to excore axial off set above 15% of RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent.

Manual SSPS functional input check every 18 months.

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8)

Deleted (9)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip wiring.

(10) -

( 11) -

(12) -

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSI>S)

Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

Perform a functional test of:

Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorders)

Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as fol~ows:

a.

response time testing, (3 times) (visicorder) trend data

b.

trip bar lift force measurements

c.

UV output force measurement

d.

dropout voltage check

e.

servicing/lubrication/adjustments (See Table 3.3-1 Notation 1111#)

f.

repeat testing steps (a-d) following any necessary actions at step (e)

SALEM - UNIT 1 3/4 3-13 Amendment No. 97

TABLE 3.3-1 (Continuedl

.Ul

):a llEACTOR TRlP SYSTEM INSTRUMENTATION r-ni

s::

MlNlMUM c

TOTAL NUMBER

-CHANNELS CHANNELS APPLJCABLE

z TO TRl.t_

FUNCTIONAL UNIT OF CllAN~ELS _

OPERABLE-

___ MQDE~ ____

ACT_ ION

-I N

18. - Turbine Trip
a.

Low Autostop Oil Pressure J

2 2

ltl

b.

Turbine Stop Valve Closure 4

4 4

711

~~F

-19.

Safety Injection Input from~--

l 2

-1,l

-1

20.

Heactor Coolant Pump Breaker 1/breaker 1/breaker 11 Position Trip (above P-7>

per ope1-a-w ting loop w

I....

21.

Reactor Trip Breakers 2

1 2

1

  • 2 11/liil. 14 3*,4*,5*

13

22.

Automatic Trip Logic 2

1 2

1

  • 2 1

3*,4*,5*

13 e

TABLE 4.3-1 (Continuecti

(./)

)::>

flliAC'!OJL11HP __ ;-;ySTEt1 JN~'I'RUMEN'I~i\\'J'JON SURVEILLANCE ~-J H~'fl;i r

fT1 3:

CHANNEL MODES IN WHICH c

CHANNEL FUNCTIONAL SUHVEILLANCE

  • 1
z FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

-I N

'13.

Loss of Flow - Two Loops s

R N.A.

14.

Steam Generator Water Level--

s k

M 1

  • 2
  • e

.Low-Low

15.

Steai11/l*'eedwate1 Flow Mism;it<:h &

~

R M

I, 2 Low Stearn Generator Water Level

16.

Undervoltage -

Re.le Lor Coolant N.A.

R M.

CJ.)

Pumps

.i:a.

CJ.)

I

17.

Underf requency Reactor Coolant N.A.

R M

1 N

Pumps

18.

Turbine Trip

a.

Low Autostop Oil Pressure N.A.

N.A.

S/U( 1)

N.A.

b.

Turbine Stop Valve Closure N.A.

N.A.

S/U( 1) f!i5J N.A.

P§F M(4)/(bJ e

19.

Safety Injection Input from ~s N.A.

N.A.

1, 2

)::>

ffi

20.

Reactor Coolant Pump Breaker N.A.

N.A.

R

s N.A.
a.

Position Trip 3

{I)

s r+
21.

Reactor Trip Breaker N.A.

N.A.

S/U( 10),

1, 2 and *

z M(11,13),

0.

SA( 12, 13)

.i:a.

and R(14)

22.

Automatic Trip Logic N.A.

N.A.

M(5) 1 ' 2 and

  • r (1)

TABLE 4.3-1 (Continued)

NOTATION

  • With the readtor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

(2)

Heat balance only, above 15% of RATED THERMAL POWER.

(3)

Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent.

-c(nfo

<4 )

Manual SSPS functional input check every 18 months.

Ofl /y,.

(5)

Jo e-hoJ1J'7f" Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

f;- ~'5 (6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

r~<?.

en Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8)

Deleted (9)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip wiring.

(10) -

( 11) -

(12) -

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS)

Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

Perform a functional test of:

Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorders)

Reactor Trip Breaker Shunt Trip (via manual.pushbutton controls)

Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:

a.
b.
c.

d

  • response time testing, (3 times) (visicorder) trend data trip bar lift force measurements U.V. output force measurement dropout voltage check SALEM - UNIT 2 3/4 3-13 Amendment No. 74
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